Evaluation of the Neutron Data Standards
Evaluation of the Neutron Data Standards
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DOI：
10.1016/j.nds.2018.02.002
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发表时间：
2018-02-01
影响因子：
3.7
通讯作者：
Wang, W.
中科院分区：
文献类型：
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作者：
Carlson, A. D.;Pronyaev, V. G.;Wang, W.
鉴于需要改进现有的核数据评估(例如，ENDF/B-VIII.0和Jeff-3.3版本)，第一步是评估在这种资料库中使用的标准。这项新的标准评估利用了改进的实验数据和分析和评估方法的一些进展。除了传统标准的工作外，这项工作还扩展了一些能量范围，并包括了被称为参考截面的新反应。由于这项工作超出了传统标准，因此被称为中子数据标准评估。这项国际努力对下列横截面标准进行了新的评估：H(n，n)、Li-6(n，t)、B-10(n，α)、B-10(n，α(1)伽马)、C-NAT(n，n)、Au(n，伽马)、U-235(n，f)和U-238(n，f)。在评估过程中，还对非标准的U-238(n，伽马)和Pu-239(n，f)截面进行了评估。还对非传统标准数据进行了评估：30keV时Au(n，伽马)截面的Maxwell谱平均截面；快中子诱导反应中产生瞬发伽马射线的参考截面；甚高能裂变截面的参考截面；由热入射中子引起的CF-252自发裂变中子谱和U-235瞬时裂变中子谱；以及热中子常数。不确定度的数据和协方差矩阵直接从评估过程中获得。
With the need for improving existing nuclear data evaluations, (e.g., ENDF/B-VIII.0 and JEFF-3.3 releases) the first step was to evaluate the standards for use in such a library. This new standards evaluation made use of improved experimental data and some developments in the methodology of analysis and evaluation. In addition to the work on the traditional standards, this work produced the extension of some energy ranges and includes new reactions that are called reference cross sections. Since the effort extends beyond the traditional standards, it is called the neutron data standards evaluation. This international effort has produced new evaluations of the following cross section standards: the H(n,n), Li-6(n,t), B-10(n, alpha), B-10(n,alpha(1)gamma), C-nat(n,n), Au(n,gamma), U-235(n,f) and U-238(n,f). Also in the evaluation process the U-238(n,gamma) and Pu-239(n,f) cross sections that are not standards were evaluated. Evaluations were also obtained for data that are not traditional standards: the Maxwellian spectrum averaged cross section for the Au(n,gamma) cross section at 30 keV; reference cross sections for prompt gamma-ray production in fast neutron-induced reactions; reference cross sections for very high energy fission cross sections; the Cf-252 spontaneous fission neutron spectrum and the U-235 prompt fission neutron spectrum induced by thermal incident neutrons; and the thermal neutron constants. The data and covariance matrices of the uncertainties were obtained directly from the evaluation procedure.